IAD Method Applied to Reactor Physics Problems

The neutron diffusion equations depen on the space and time with multi-group of delayed neutrons are a couple of the stiff nonlinear partial differential equations. Application of finite difference method for simplified equations to partial differential equations often, then be rewritten as a matrix form. The general solution of the matrix differential equation contains the exponential function of the coeffcient matrix. The numerical techniques for processing the exponential function of the coeffcient matrix are presented using an alytical method and fundamental matrix method. Method IAD (average method integral derivative) to define the boundary conditions for the specific geometry of the reactor. Eigenvalues matrix coefficients are calculated by MATLAB program. Numerical results are compared with the other results.